TRANSIENT HEATING OF UC FUEL ELEMENTS IN THE KEWB FACILITY | Zendy

E.L. Gardner | Zendy; S G Barnes | Zendy

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TRANSIENT HEATING OF UC FUEL ELEMENTS IN THE KEWB FACILITY

Author(s) -

E.L. Gardner,

S G Barnes

Publication year - 1959

Publication title -

osti oai (u.s. department of energy office of scientific and technical information)

Language(s) - English

Resource type - Reports

DOI - 10.2172/4182403

Subject(s) - thermocouple , transient (computer programming) , nuclear engineering , neutron flux , research reactor , materials science , thermal conductivity , neutron temperature , heat flux , neutron , mechanics , nuclear physics , heat transfer , engineering , physics , composite material , computer science , operating system

The feasibility of using the KEWB reactor as a pulsed neutron radiation source for use in studies of fuel element transient heating was studied. UC fuel rod samples were heated in the reactor. It was found that flux distribution in fuel samples could be mapped and thermal conductivity measurements for UC could be made by using fast response thermocouples distributed radially in the sample. (J. R.D.

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